Validation of coupled codes for VVERs by analysis of plant transients

R. Mittag; S. Kliem; F.P. Weiss; Riitta Kyrki-Rajamäki; Anitta Hämäläinen; S. Langenbuch; S. Danilin; J. Hadek; G. Hegyi; A. Kuchin; D. Panayotov

Validation of coupled codes for VVERs by analysis of plant transients

R. Mittag
, S. Kliem
, F.P. Weiss
, Riitta Kyrki-Rajamäki
, Anitta Hämäläinen
, S. Langenbuch
, S. Danilin
, J. Hadek
, G. Hegyi
, A. Kuchin
, D. Panayotov

Forschungszentrum Rossendorf (FZR)
Gesellschaft für Anlagen- und Reaktorsicherheit (GRS) gGmbH
ÚJV Řež a.s.
HUN-REN Centre for Energy Research (HUN-REN EK)
Petersburg Nuclear Physics Institute
State Scientific and Technical Center for Nuclear and Radiation Safety (SSTC NRS)
Institute of Nuclear Research and Nuclear Energy (INRNE)

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Professional

Original language	English
Title of host publication	Advanced Thermal-hydraulic and Neutronic Codes: Current and Future Applications
Subtitle of host publication	Workshop Proceedings
Publisher	OECD NEA Nuclear Energy Agency
Pages	309-324
Publication status	Published - 2001
MoE publication type	D3 Professional conference proceedings
Event	OECD/CSNI Workshop on Advanced Thermal-Hydraulic and Neutronic Codes: Current and Future Applications - Barcelona, Spain Duration: 10 Apr 2000 → 13 Apr 2000

Publication series

Series	NEA Committee on the Safety of Nuclear Installations. Report
Number	NEA/CSNI/R(2001)2/VOL1

Workshop

Workshop	OECD/CSNI Workshop on Advanced Thermal-Hydraulic and Neutronic Codes
Country/Territory	Spain
City	Barcelona
Period	10/04/00 → 13/04/00

Access to Document

https://www.oecd-nea.org/nsd/docs/2001/csni-r2001-2-vol1.pdf

Cite this

Mittag, R., Kliem, S., Weiss, F. P., Kyrki-Rajamäki, R., Hämäläinen, A., Langenbuch, S., Danilin, S., Hadek, J., Hegyi, G., Kuchin, A., & Panayotov, D. (2001). Validation of coupled codes for VVERs by analysis of plant transients. In Advanced Thermal-hydraulic and Neutronic Codes: Current and Future Applications: Workshop Proceedings (pp. 309-324). OECD NEA Nuclear Energy Agency. https://www.oecd-nea.org/nsd/docs/2001/csni-r2001-2-vol1.pdf

@inproceedings{edc7779cffd943028a41a4a84a646460,

title = "Validation of coupled codes for VVERs by analysis of plant transients",

author = "R. Mittag and S. Kliem and F.P. Weiss and Riitta Kyrki-Rajam{\"a}ki and Anitta H{\"a}m{\"a}l{\"a}inen and S. Langenbuch and S. Danilin and J. Hadek and G. Hegyi and A. Kuchin and D. Panayotov",

year = "2001",

language = "English",

series = "NEA Committee on the Safety of Nuclear Installations. Report",

publisher = "OECD NEA Nuclear Energy Agency",

number = "NEA/CSNI/R(2001)2/VOL1",

pages = "309--324",

booktitle = "Advanced Thermal-hydraulic and Neutronic Codes: Current and Future Applications",

address = "France",

note = "OECD/CSNI Workshop on Advanced Thermal-Hydraulic and Neutronic Codes : Current and Future Applications ; Conference date: 10-04-2000 Through 13-04-2000",

}

Mittag, R, Kliem, S, Weiss, FP, Kyrki-Rajamäki, R, Hämäläinen, A, Langenbuch, S, Danilin, S, Hadek, J, Hegyi, G, Kuchin, A & Panayotov, D 2001, Validation of coupled codes for VVERs by analysis of plant transients. in Advanced Thermal-hydraulic and Neutronic Codes: Current and Future Applications: Workshop Proceedings. OECD NEA Nuclear Energy Agency, NEA Committee on the Safety of Nuclear Installations. Report, no. NEA/CSNI/R(2001)2/VOL1, pp. 309-324, OECD/CSNI Workshop on Advanced Thermal-Hydraulic and Neutronic Codes, Barcelona, Spain, 10/04/00. <https://www.oecd-nea.org/nsd/docs/2001/csni-r2001-2-vol1.pdf>

Validation of coupled codes for VVERs by analysis of plant transients. / Mittag, R.; Kliem, S.; Weiss, F.P. et al.
Advanced Thermal-hydraulic and Neutronic Codes: Current and Future Applications: Workshop Proceedings. OECD NEA Nuclear Energy Agency, 2001. p. 309-324 (NEA Committee on the Safety of Nuclear Installations. Report; No. NEA/CSNI/R(2001)2/VOL1).

Research output: Chapter in Book/Report/Conference proceeding › Conference article in proceedings › Professional

TY - GEN

T1 - Validation of coupled codes for VVERs by analysis of plant transients

AU - Mittag, R.

AU - Kliem, S.

AU - Weiss, F.P.

AU - Kyrki-Rajamäki, Riitta

AU - Hämäläinen, Anitta

AU - Langenbuch, S.

AU - Danilin, S.

AU - Hadek, J.

AU - Hegyi, G.

AU - Kuchin, A.

AU - Panayotov, D.

PY - 2001

Y1 - 2001

M3 - Conference article in proceedings

T3 - NEA Committee on the Safety of Nuclear Installations. Report

SP - 309

EP - 324

BT - Advanced Thermal-hydraulic and Neutronic Codes: Current and Future Applications

PB - OECD NEA Nuclear Energy Agency

T2 - OECD/CSNI Workshop on Advanced Thermal-Hydraulic and Neutronic Codes

Y2 - 10 April 2000 through 13 April 2000

ER -

Mittag R, Kliem S, Weiss FP, Kyrki-Rajamäki R, Hämäläinen A, Langenbuch S et al. Validation of coupled codes for VVERs by analysis of plant transients. In Advanced Thermal-hydraulic and Neutronic Codes: Current and Future Applications: Workshop Proceedings. OECD NEA Nuclear Energy Agency. 2001. p. 309-324. (NEA Committee on the Safety of Nuclear Installations. Report; No. NEA/CSNI/R(2001)2/VOL1).